This invention generally concerns radioactive decontamination of deposits on components in a nuclear power plant and is specifically concerned with improved compositions, systems and methods for disrupting, dissolving, removing and reducing at ambient temperature radionuclides formed on the primary side surfaces of components in a pressurized water reactor and the internal components of a boiling water reactor. The methods include identifying the structure, taking the structure out of operational service, contacting the structure with an aqueous solution (e.g., a recirculating flow or static immersion), and adding an effective amount of elemental metal in solid form to the aqueous solution.

A method of follow-up decontamination operation for the polluted storage canister of a high activity nuclear waste storage facility, using needle and steel brushes driven by pneumatic tools for abrading the bottom and the inner wall of the storage canister to remove contaminants, a multi-level filter system for air filtration and removing pollutants in the storage canister, and a cover to be used in association with the pneumatic tools and the multi-level filtration system suitable to cap the storage canister, thus effectively block the exposure of contaminant of the storage canister to the external environment, achieving effective decontamination of the radioactive waste and reducing spreading to the environment.

A method of follow-up decontamination operation for the polluted storage canister of a high activity nuclear waste storage facility, using needle and steel brushes driven by pneumatic tools for abrading the bottom and the inner wall of the storage canister to remove contaminants, a multi-level filter system for air filtration and removing pollutants in the storage canister, and a cover to be used in association with the pneumatic tools and the multi-level filtration system suitable to cap the storage canister, thus effectively block the exposure of contaminant of the storage canister to the external environment, achieving effective decontamination of the radioactive waste and reducing spreading to the environment.

The invention relates to an apparatus for treating waste material including organic components and radioactive agents. In the apparatus the waste material including organic components and radioactive agents are gasified at temperature between 600-950° C. in a fluidized bed reactor to form a gaseous material. The gaseous material is than cooled in a water quenching device so that temperature is between 300-500° C. after the cooling. The solid fraction including radioactive agents is removed from the gaseous material in a in at least one filtration device. A gas scrubbing device then removes sulphur by scrubbing the treated gaseous material after the filtration in order to form a treated gaseous material.

A method of decontaminating a metal surface located on a component within a nuclear plant, in particular within the cooling system of a nuclear power plant, which is covered with a metal oxide layer containing radioactive substances, the method including a decontamination step in which a metal oxide layer pretreated in an oxidation step is contacted with an aqueous solution of an organic acid to dissolve the metal oxide layer, forming a decontamination solution containing the organic acid, metal ions and the radioactive substances, and passing the decontamination solution over an ion exchanger to immobilize metal ions and radioactive substances. An oxidant selected from oxygen, air, hydrogen peroxide and ozone is dosed into the decontamination solution to control the dissolution rate of the metal oxide layer. The method is particularly suitable for large-scale system decontamination and ensures high process stability.

The present invention relates to a composition for transmuting a radioactive substance into a non-radioactive substance using complex microorganisms and a method for preparing the composition.

The invention concerns an apparatus and a method for treating radioactive material (36), in particular for cleaning radioactive contaminated water. The apparatus comprises a process chamber (10) with a combustion zone (12) for generating an oxygen rich gas (34) and an oxidation zone (14), which is arranged to receive the oxygen rich gas (34) from the combustion zone (12). The process chamber (10) further comprises a feed opening (16) for feeding the radioactive material (36) into the oxidation zone (14) and the process chamber (10) is configured to use the oxygen rich gas (34) for oxidizing the radioactive material (36) to obtain oxidized material (38). The apparatus further comprises a separation device (50) operationally connected to an outlet of the process chamber (10) and configured to at least partly separate the oxidized material (38) into a gaseous fluid (56) and a non.sup.− gaseous residue (58). This way a greatly reduced volume of the radioactive material (36) is achieved, enabling safe and efficient handling and/or compact and space-saving disposal of the radioactive material (36).

The invention is intended for integrated decontamination of soils contaminated with mercury (amalgam) or/and radionuclides. Method for soil decontamination includes preparation of pulp by mixing soils with water at the soil sampling point with separation of fraction with fragments more than 100 mm in the pulp preparation module, disintegration of pulp and soil aggregates in the disintegration module with separation of plants residues and fraction with fragments more than 10 mm. Pulp thickening. In the hydroclassification module the pulp is separated into sand and fine particle fractions, the fine particle fraction goes to the dehydration module, designed as a concentrator, where it is thickened and dehydrated for further disposal. If mercury and amalgam are present in soils they are separated in the thickening module. Technical result—implementation of a low-waste nonchemical technology for decontamination of soil from mercury, its water-insoluble forms, amalgam or/and radionuclides in a single technological process without equipment resetting, separation of metal mercury or its amalgam.

This application discloses the method for separating element or isotopes such as protactinium and gallium and isotopes thereof from a corresponding mixture which method comprises contacting the mixture with a carbon-based separation material, wherein the carbon-based separation material selectively associates with the element or isotope thereof.

A mobile melting device for consolidating contaminated scrap and to a corresponding method. The melting device has a crucible chamber and a crucible base. The crucible is arranged on the crucible base during operation, and the crucible base and the crucible chamber together form a gas-tight furnace housing. It is thus possible to carry out the method in a vacuum or under protective gas such that even a reactive material can be consolidated. The melting device can be assembled and disassembled with little effort.